Development and verification of depletion capabilities in the iMC Monte Carlo code

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-02-22 DOI:10.1016/j.anucene.2025.111260

Inyup Kim, Taesuk Oh, Yonghee Kim

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Abstract

This paper presents the development, optimization, and verification of a depletion module integrated into the iMC Monte Carlo code. Several techniques are implemented to improve the performance and accuracy of the iMC depletion module. In addition, the nuclide control for the depletion of the molten salt reactors is developed. The performance of the depletion module is rigorously assessed through comprehensive code-to-code comparisons with the pre-validated Monte Carlo code Serpent. The evaluation encompasses three distinct depletion scenarios: a single PWR fuel pin, a single SFR fuel pin, and VERA benchmarks. Furthermore, the analysis extends to a simplified molten salt reactor experiment (MSRE) model, incorporating nuclide removal techniques. Comparisons focus on burnup-dependent infinite multiplication factors (k_inf) and nuclide densities of actinides and fission products. Results demonstrate both the high accuracy and enhanced efficiency of the iMC Monte Carlo code’s depletion module, marking a significant advancement in advanced reactor analysis capabilities.

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开发和验证损耗能力在iMC蒙特卡罗代码

本文提出了开发，优化，并验证了耗尽模块集成到iMC蒙特卡罗代码。采用了几种技术来提高iMC耗尽模块的性能和精度。此外，还研究了熔盐堆耗损的核素控制方法。通过与预先验证的蒙特卡罗代码Serpent进行全面的代码对代码比较，严格评估耗尽模块的性能。评估包括三种不同的耗尽情景：单个压水堆燃料引脚、单个SFR燃料引脚和VERA基准。此外，分析扩展到一个简化的熔盐堆实验（MSRE）模型，纳入核素去除技术。比较集中于燃烧依赖的无限增殖因子（kinf）和锕系元素和裂变产物的核素密度。结果表明，iMC蒙特卡罗代码的损耗模块具有较高的准确性和更高的效率，标志着先进反应堆分析能力的重大进步。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.